RELAP5/MOD2. [PWR]
Conference
·
OSTI ID:5624634
RELAP5/MOD2 is a pressurized water reactor (PWR) system transient analysis code that has been designed for use in the US Nuclear Regulatory Commission (USNRC) Safety Research and Regulatory Programs. The code is an extension of the RELAP5/MOD1 capability to include simulation of PWR transients up to the point of fuel damage. For analysis of transients involving fuel damage, RELAP5 is being coupled with the SCDAP code, which will permit analysis up to the point of vessel melt through. The improved capability of RELAP5/MOD2 compared to the earlier version is a result of continued improvement of the hydrodynamic models, added user convenience features, and addition of new component models. To a large extent, the new capability has been obtained through logical extension of the RELAP5/MOD1 modeling. As a result, the basic code structure is the same and system model input decks developed for RELAP5/MOD1 are compatible with the RELAP5/MOD2 input requirements, with minor exceptions.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5624634
- Report Number(s):
- EGG-M-20783; CONF-8310143-36; ON: DE84002214
- Country of Publication:
- United States
- Language:
- English
Similar Records
RELAP5/MOD2: for PWR transient analysis
RELAP5/MOD2 pressurizer modeling
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Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5658636
RELAP5/MOD2 pressurizer modeling
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6192347
Assessment of PWR Steam Generator modelling in RELAP5/MOD2. International Agreement Report
Technical Report
·
Tue Jun 01 00:00:00 EDT 1993
·
OSTI ID:10168879
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
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COMPUTER CALCULATIONS
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDRODYNAMICS
INFORMATION
MECHANICS
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PRESSURE GRADIENTS
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REACTOR SAFETY
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TEMPERATURE GRADIENTS
THEORETICAL DATA
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VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTER CALCULATIONS
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDRODYNAMICS
INFORMATION
MECHANICS
NUMERICAL DATA
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
THEORETICAL DATA
TRANSIENTS
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS